US4735768A - Fuel rod for a nuclear reactor fuel assembly - Google Patents

Fuel rod for a nuclear reactor fuel assembly Download PDF

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Publication number
US4735768A
US4735768A US06/894,922 US89492286A US4735768A US 4735768 A US4735768 A US 4735768A US 89492286 A US89492286 A US 89492286A US 4735768 A US4735768 A US 4735768A
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Prior art keywords
zirconium alloy
iron
weight
fuel rod
fuel
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Expired - Lifetime
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US06/894,922
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Heinz Stehle
Eckard Steinberg
Hans Weidinger
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Areva GmbH
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Kraftwerk Union AG
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Assigned to SIEMENS AKTIENGESELLSCHAFT, BERLIN AND MUNICH, GERMANY, A JOINT STOCK COMPANY reassignment SIEMENS AKTIENGESELLSCHAFT, BERLIN AND MUNICH, GERMANY, A JOINT STOCK COMPANY MERGER (SEE DOCUMENT FOR DETAILS). EFFECTIVE 07-31-87 Assignors: KRAFTWERK UNION AKTIENGESELLSCHAFT, (MERGED INTO)
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Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02—Fuel elements
    • G21C3/04—Constructional details
    • G21C3/06—Casings; Jackets
    • G21C3/07—Casings; Jackets characterised by their material, e.g. alloys
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • Such fuel rods are in common use. They are built into the frame of the nuclear reactor fuel assembly. This nuclear reactor fuel assembly is finally inserted into a nuclear reactor, in which it is cooled, for instance, with light water. In this nuclear reactor, the zirconium alloys of the cladding tubes have a relatively small capture cross section for thermal neutrons.
  • a fuel rod for a nuclear reactor fuel assembly with nuclear fuel which is contained in a cladding tube comprising an inner tubular layer formed of a zirconium alloy with alloying components based on the weight of the zirconium alloy of 1.2 to 1.7% tin, 0.07 to 0.2% iron, 0.05 to 0.15% chromium, 0.03 to 0.08% nickel, 0.07 to 0.15% oxygen, with the sum of percentages for the alloying components iron, chromium and nickel in the range of 0.18 to 0.38%; the combination therewith of a surface layer on the outside of the inner tubular layer of a second zirconium alloy with a layer thickness in the range of 5 to 20% of the total wall thickness of the cladding tube as well as with 0 to 1% by weight iron based on the second zirconium alloy as an alloying component and with at least one alloying component selected from the group consisting of vanadium, platinum and copper wherein the amounts by weight
  • a fuel rod for a nuclear reactor fuel assembly with nuclear fuel which is contained in a cladding tube comprising an inner tubular layer formed of a zirconium alloy with alloying components based on the weight of the zirconium alloy of 1.2 to 1.7% tin, 0.18 to 0.24% iron, 0.07 to 0.13% chromium, 0.10 to 0.16% oxygen, with the sum of percentages for the alloying components iron, and chromium in the range of 0.28 to 0.37%; the combination therewith of a surface layer on the outside of the inner tubular layer of a second zirconium alloy with a layer thickness in the range of 5 to 20% of the total wall thickness of the cladding tube as well as with 0 to 1% by weight iron based on the second zirconium alloy as an alloying component and with at least one alloying component selected from the group consisting of vanadium, platinum and copper wherein the amounts by weight based on the second zirconium alloy are: vanadium--0.1
  • the invention is based on the insight that the zirconium alloy of which the surface layer on the outside of the cladding tube of this fuel rod consists, is more corrosion-resistant than the zirconium alloy of which the rest of the cladding tube consists. While furthermore, the capture cross section of vanadium, platinum and copper for thermal neutrons is relatively large and the three mentioned alloying components are present only in the relatively thin surface layer of the cladding tube, the absorption losses of thermal neutrons in the nuclear reactor due to the cladding tubes are nevertheless relatively small.
  • Tests in an autoclave showed that the rate of corrosion of a test specimen of a zirconium alloy with 0.5% by weight iron and 0.25% by weight vanadium as the alloying components in steam is only one-tenth of the corrosion rate of a test specimen of a zirconium alloy with the trade name Zircaloy 4 under the same conditions, which contains, besides the zirconium, 1.2 to 1.7% tin, 0.18 to 0.24% iron, 0.07 to 0.13% chromium and 0.1 to 0.16% oxygen as further alloying components and in which the sum of the percentages by weight of the alloying components iron and chromium is in the range from 0.28 to 0.37% by weight.
  • the dwelling time of a nuclear reactor fuel assembly with fuel rods according to the invention in a nuclear reactor can therefore be at least one year longer than that of a nuclear reactor fuel assembly with fuel rods, the cladding tubes of which consist of Zircaloy 4.
  • a tube blank which comprises an inner tube, for instance, of Zircaloy 4 and an outer tube placed on this inner tube, of the zirconium-vanadium-iron alloy with 0.5% by weight iron and 0.25% by weight vanadium.
  • This tube blank is heated to a temperature in the range of 500° to 700° C. and is then extruded. In the process, a metallurgical compound between the two zirconium alloys results.
  • the final cladding tube for the fuel rod is ultimately obtained, which can, for instance, have a diameter of 10.7 mm and a wall thickness of 0.72 mm.
  • the surface layer of the vanadium-containing zirconium alloy cover the entire outside of this cladding tube and may be, for instance, 0.1 mm thick.
  • a pilger-rolling mill is described, for instance, in U.S. Pat. No. 42 33 834.

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  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Metallurgy (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Catalysts (AREA)

Abstract

Fuel rod cladding tube having an inner tubular layer of a zirconium alloy with alloying components of 1.2 to 1.7% tin, 0.07 to 0.2% iron, 0.05 to 0.15% chromium, 0.03 to 0.08% nickel, 0.07 to 0.15% oxygen, with the sum of percentages of iron, chromium and nickel in the range of 0.18 to 0.38%; or with the alloying components 1.2 to 1.7% tin, 0.18 to 0.24% iron, 0.07 to 0.13% chromium, 0.10 to 0.16% oxygen, with the sum of percentages of iron and chromium in the range of 0.28 to 0.37%; and with the inner tubular layer having an outside surface layer of another zirconium alloy with a layer thickness of 5 to 20% of the cladding tube as well as with 0 to 1% iron as an alloying component and with at least one alloying component from the group of: vanadium with 0.1 to 1% by weight, platinum with 0.1 to 1% by weight, and copper with 1 to 3% by weight.

Description

BACKGROUND OF THE INVENTION
1. Field of the Invention
The invention relates to a fuel rod for a nuclear reactor fuel assembly with nuclear fuel which is contained in a cladding tube which is formed of a zirconium alloy.
2. Description of the Prior Art
Such fuel rods are in common use. They are built into the frame of the nuclear reactor fuel assembly. This nuclear reactor fuel assembly is finally inserted into a nuclear reactor, in which it is cooled, for instance, with light water. In this nuclear reactor, the zirconium alloys of the cladding tubes have a relatively small capture cross section for thermal neutrons.
On the outside of the cladding tubes of the fuel rods, corrosion takes place during the operation in the nuclear reactor, which limits the ability of the nuclear reactor fuel assembly to dwell in the nuclear reactor time-wise. The usual dwelling times are three to four years.
SUMMARY OF THE INVENTION
It is an object of the invention to improve the dwelling time of such nuclear reactor fuel assemblies to prolong their insertion in the nuclear reactor.
With the foregoing and other objects in view, there is provided in accordance with the invention a fuel rod for a nuclear reactor fuel assembly with nuclear fuel which is contained in a cladding tube comprising an inner tubular layer formed of a zirconium alloy with alloying components based on the weight of the zirconium alloy of 1.2 to 1.7% tin, 0.07 to 0.2% iron, 0.05 to 0.15% chromium, 0.03 to 0.08% nickel, 0.07 to 0.15% oxygen, with the sum of percentages for the alloying components iron, chromium and nickel in the range of 0.18 to 0.38%; the combination therewith of a surface layer on the outside of the inner tubular layer of a second zirconium alloy with a layer thickness in the range of 5 to 20% of the total wall thickness of the cladding tube as well as with 0 to 1% by weight iron based on the second zirconium alloy as an alloying component and with at least one alloying component selected from the group consisting of vanadium, platinum and copper wherein the amounts by weight based on the second zirconium alloy are: vanadium--0.1 to 1%; platinum--0.1 to 1%; and copper--1 to 3%.
In accordance with the invention, there is provided a fuel rod for a nuclear reactor fuel assembly with nuclear fuel which is contained in a cladding tube comprising an inner tubular layer formed of a zirconium alloy with alloying components based on the weight of the zirconium alloy of 1.2 to 1.7% tin, 0.18 to 0.24% iron, 0.07 to 0.13% chromium, 0.10 to 0.16% oxygen, with the sum of percentages for the alloying components iron, and chromium in the range of 0.28 to 0.37%; the combination therewith of a surface layer on the outside of the inner tubular layer of a second zirconium alloy with a layer thickness in the range of 5 to 20% of the total wall thickness of the cladding tube as well as with 0 to 1% by weight iron based on the second zirconium alloy as an alloying component and with at least one alloying component selected from the group consisting of vanadium, platinum and copper wherein the amounts by weight based on the second zirconium alloy are: vanadium--0.1 to 1%; platinum--0.1 to 1%; and copper--1 to 3%.
Other features which are considered as characteristic for the invention are set forth in the appended claims.
Although the invention is illustrated and described herein as embodied in a fuel rod for a nuclear reactor fuel assembly, it is nevertheless not intended to be limited to the details shown, since various modifications may be made therein without departing from the spirit of the invention and within the scope and range of equivalents of the claims.
DESCRIPTION OF THE PREFERRED EMBODIMENTS
The invention is based on the insight that the zirconium alloy of which the surface layer on the outside of the cladding tube of this fuel rod consists, is more corrosion-resistant than the zirconium alloy of which the rest of the cladding tube consists. While furthermore, the capture cross section of vanadium, platinum and copper for thermal neutrons is relatively large and the three mentioned alloying components are present only in the relatively thin surface layer of the cladding tube, the absorption losses of thermal neutrons in the nuclear reactor due to the cladding tubes are nevertheless relatively small.
Tests in an autoclave showed that the rate of corrosion of a test specimen of a zirconium alloy with 0.5% by weight iron and 0.25% by weight vanadium as the alloying components in steam is only one-tenth of the corrosion rate of a test specimen of a zirconium alloy with the trade name Zircaloy 4 under the same conditions, which contains, besides the zirconium, 1.2 to 1.7% tin, 0.18 to 0.24% iron, 0.07 to 0.13% chromium and 0.1 to 0.16% oxygen as further alloying components and in which the sum of the percentages by weight of the alloying components iron and chromium is in the range from 0.28 to 0.37% by weight. The dwelling time of a nuclear reactor fuel assembly with fuel rods according to the invention in a nuclear reactor can therefore be at least one year longer than that of a nuclear reactor fuel assembly with fuel rods, the cladding tubes of which consist of Zircaloy 4.
In the manufacture of a cladding tube for a fuel rod according to the invention, one advantageously starts out with a tube blank which comprises an inner tube, for instance, of Zircaloy 4 and an outer tube placed on this inner tube, of the zirconium-vanadium-iron alloy with 0.5% by weight iron and 0.25% by weight vanadium. This tube blank is heated to a temperature in the range of 500° to 700° C. and is then extruded. In the process, a metallurgical compound between the two zirconium alloys results.
By subsequent pilger-rolling of the extruded body, the final cladding tube for the fuel rod is ultimately obtained, which can, for instance, have a diameter of 10.7 mm and a wall thickness of 0.72 mm. The surface layer of the vanadium-containing zirconium alloy cover the entire outside of this cladding tube and may be, for instance, 0.1 mm thick. A pilger-rolling mill is described, for instance, in U.S. Pat. No. 42 33 834.
The foregoing is a description corresponding, in substance, to German application P 35 28 545.1, dated Aug. 8, 1985, international priority of which is being claimed for the instant application and which is hereby made part of this application. Any material discrepancies between the foregoing specification and the specification of the aforementioned corresponding German application are to be resolved in favor of the latter.

Claims (8)

We claim:
1. Fuel rod for a nuclear reactor fuel assembly with nuclear fuel which is contained in a cladding tube formed of a zirconium alloy with alloying components based on the weight of the zirconium alloy of 1.2 to 1.7% tin, 0.07 to 0.2% iron, 0.05 to 0.15% chromium, 0.03 to 0.08% nickel, 0.07 to 0.15% oxygen, with the sum of percentages for the alloying components iron, chromium and nickel in the range of 0.18 to 0.38%; and with a surface layer on the outside of the cladding tube formed of a second zirconium alloy with a layer thickness in the range of 5 to 20% of the total wall thickness of the cladding tube as well as with 0 to 1% by weight iron based on the second zirconium alloy as an alloying component and with at least one alloying component selected from the group consisting of vanadium, platinum and copper wherein the amounts by weight based on the second zirconium alloy are: vanadium--0.1 to 1%; platinum--0.1 to 1%; and copper--1 to 3%.
2. Fuel rod for a nuclear reactor fuel assembly with nuclear fuel which is contained in a cladding tube formed of a zirconium alloy with alloying components based on the weight of the zirconium alloy of 1.2 to 1.7% tin, 0.18 to 0.24% iron, 0.07 to 0.13% chromium, 0.10 to 0.16% oxygen, with the sum of percentages for the alloying components iron and chromium in the range of 0.28 to 0.37%; and with a surface layer on the outside of the cladding tube formed of a second zirconium alloy with a layer thickness in the range of 5 to 20% of the total wall thickness of the cladding tube as well as with 0 to 1% by weight iron based on the second zirconium alloy as an alloying component and with at least one alloying component selected from the group consisting of vanadium, platinum and copper wherein the amounts by weight based on the second zirconium alloy are: vanadium--0.1 to 1%; platinum--0.1 to 1%; and copper--1 to 3%.
3. Fuel rod according to claim 1, wherein the alloying component of the second zirconium alloy is vanadium in an amount of 0.1 to 1%.
4. Fuel rod according to claim 1, wherein the alloying component of the second zirconium alloy is platinum in an amount of 0.1 to 1%.
5. Fuel rod according to claim 1, wherein the alloying component of the second zirconium alloy is copper in an amount of 1 to 3%.
6. Fuel rod according to claim 2, wherein the alloying component of the second zirconium alloy is vanadium in an amount of 0.1 to 1%.
7. Fuel rod according to claim 2, wherein the alloying component of the second zirconium alloy is platinum in an amount of 0.1 to 1%.
8. Fuel rod according to claim 2, wherein the alloying component of the second zirconium alloy is copper in an amount of 1 to 3%.
US06/894,922 1985-08-08 1986-08-08 Fuel rod for a nuclear reactor fuel assembly Expired - Lifetime US4735768A (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE3528545 1985-08-08
DE19853528545 DE3528545A1 (en) 1985-08-08 1985-08-08 FUEL ROD FOR A CORE REACTOR FUEL

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EP (1) EP0212351B1 (en)
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DE (2) DE3528545A1 (en)

Cited By (25)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4775508A (en) * 1985-03-08 1988-10-04 Westinghouse Electric Corp. Zirconium alloy fuel cladding resistant to PCI crack propagation
US4816214A (en) * 1987-10-22 1989-03-28 Westinghouse Electric Corp. Ultra slow EB melting to reduce reactor cladding
US4933136A (en) * 1985-03-08 1990-06-12 Westinghouse Electric Corp. Water reactor fuel cladding
US4938921A (en) * 1987-06-23 1990-07-03 Framatome Method of manufacturing a zirconium-based alloy tube for a nuclear fuel element sheath and tube thereof
US4938920A (en) * 1988-02-18 1990-07-03 Siemens Aktiengesellschaft Nuclear reactor fuel assembly
US4963316A (en) * 1987-07-21 1990-10-16 Siemens Aktiengesellschaft Fuel rod for a nuclear reactor fuel assembly
US4986957A (en) * 1989-05-25 1991-01-22 General Electric Company Corrosion resistant zirconium alloys containing copper, nickel and iron
US5024809A (en) * 1989-05-25 1991-06-18 General Electric Company Corrosion resistant composite claddings for nuclear fuel rods
US5026516A (en) * 1989-05-25 1991-06-25 General Electric Company Corrosion resistant cladding for nuclear fuel rods
US5073336A (en) * 1989-05-25 1991-12-17 General Electric Company Corrosion resistant zirconium alloys containing copper, nickel and iron
US5084234A (en) * 1988-12-31 1992-01-28 Hoesgen Karlheinz Absorption casing for a source of radioactive radiation, particularly for a nuclear reactor
WO1993018520A1 (en) * 1992-03-13 1993-09-16 Siemens Aktiengesellschaft Nuclear reactor fuel rod with double layer cladding tube
US5247550A (en) * 1992-03-27 1993-09-21 Siemens Power Corporation Corrosion resistant zirconium liner for nuclear fuel rod cladding
US5373541A (en) * 1992-01-17 1994-12-13 Framatome Nuclear fuel rod and method of manufacturing the cladding of such a rod
US5711826A (en) * 1996-04-12 1998-01-27 Crs Holdings, Inc. Functionally gradient cladding for nuclear fuel rods
US5768332A (en) * 1997-03-27 1998-06-16 Siemens Power Corporation Nuclear fuel rod for pressurized water reactor
US5772798A (en) * 1997-03-25 1998-06-30 Siemens Power Corporation High strength zirconium alloys containing bismuth
US5787142A (en) * 1997-04-29 1998-07-28 Siemens Power Corporation Pressurized water reactor nuclear fuel assembly
US5790623A (en) * 1997-03-25 1998-08-04 Siemens Power Corporation Composite cladding for nuclear fuel rods
US5887045A (en) * 1995-01-30 1999-03-23 Framatome Zirconium alloy tube for a nuclear reactor fuel assembly, and method for making same
US6511556B1 (en) 1998-06-12 2003-01-28 Siemens Power Corporation High strength zirconium alloys containing bismuth and niobium
US20050005872A1 (en) * 2003-07-09 2005-01-13 Greeson John Stuart Automated carrier-based pest control system
US20060048869A1 (en) * 2004-09-08 2006-03-09 David White Non-heat treated zirconium alloy fuel cladding and a method of manufacturing the same
US20060048870A1 (en) * 2004-09-08 2006-03-09 David White Zirconium alloy fuel cladding for operation in aggressive water chemistry
US20110002433A1 (en) * 2006-08-24 2011-01-06 Lars Hallstadius Water Reactor Fuel Cladding Tube

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2642215B1 (en) * 1989-01-23 1992-10-02 Framatome Sa PENCIL FOR FUEL ASSEMBLY OF A CORROSION AND WEAR RESISTANT NUCLEAR REACTOR
FR2663115B1 (en) * 1990-06-08 1994-04-15 Framatome METHOD AND DEVICE FOR CONTROLLING THE THICKNESS AND THE COHESION OF THE INTERFACE OF A DUPLEX TUBE.
EP1760724A3 (en) 1999-03-29 2009-03-18 AREVA NP GmbH Fuel element for a pressurised water reactor and method for producing the cladding tubes thereof

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CH387180A (en) * 1958-02-27 1965-01-31 Atomic Energy Commission Nuclear reactor fuel element and method of manufacturing the fuel element
FR1537960A (en) * 1967-07-20 1968-08-30 Siemens Ag Process for obtaining high corrosion resistance
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US3620691A (en) * 1964-04-11 1971-11-16 Siemens Ag Zirconium structure
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FR2509510A1 (en) * 1981-07-07 1983-01-14 Asea Atom Ab METHOD FOR MANUFACTURING COATING TUBES IN A ZIRCONIUM-BASED ALLOY FOR FUEL BARS FOR NUCLEAR REACTORS
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FR2538940A1 (en) * 1982-12-30 1984-07-06 Kraftwerk Union Ag METHOD FOR MAKING A ZIRCONIUM ALLOY SHEATH FOR THE FUEL OF A NUCLEAR REACTOR COMBUSTIBLE ELEMENT
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CH387180A (en) * 1958-02-27 1965-01-31 Atomic Energy Commission Nuclear reactor fuel element and method of manufacturing the fuel element
US3620691A (en) * 1964-04-11 1971-11-16 Siemens Ag Zirconium structure
LU53851A1 (en) * 1967-06-09 1969-04-22
FR1537960A (en) * 1967-07-20 1968-08-30 Siemens Ag Process for obtaining high corrosion resistance
US4045288A (en) * 1974-11-11 1977-08-30 General Electric Company Nuclear fuel element
US4406012A (en) * 1974-11-11 1983-09-20 General Electric Company Nuclear fuel elements having a composite cladding
FR2317372A1 (en) * 1975-06-26 1977-02-04 Gen Electric PROCESS FOR IMPROVING THE CORROSION RESISTANCE OF ZIRCONIUM ALLOY PARTS AND PARTS THUS OBTAINED.
US4473410A (en) * 1977-08-01 1984-09-25 General Electric Company Nuclear fuel element having a composite coating
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US4233834A (en) * 1979-01-26 1980-11-18 Sandvik Special Metal Corporation Method and apparatus for producing zircaloy tubes and zircaloy tubes thus produced
FR2509510A1 (en) * 1981-07-07 1983-01-14 Asea Atom Ab METHOD FOR MANUFACTURING COATING TUBES IN A ZIRCONIUM-BASED ALLOY FOR FUEL BARS FOR NUCLEAR REACTORS
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Cited By (30)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4933136A (en) * 1985-03-08 1990-06-12 Westinghouse Electric Corp. Water reactor fuel cladding
US4775508A (en) * 1985-03-08 1988-10-04 Westinghouse Electric Corp. Zirconium alloy fuel cladding resistant to PCI crack propagation
US4938921A (en) * 1987-06-23 1990-07-03 Framatome Method of manufacturing a zirconium-based alloy tube for a nuclear fuel element sheath and tube thereof
US4963316A (en) * 1987-07-21 1990-10-16 Siemens Aktiengesellschaft Fuel rod for a nuclear reactor fuel assembly
US4816214A (en) * 1987-10-22 1989-03-28 Westinghouse Electric Corp. Ultra slow EB melting to reduce reactor cladding
US4938920A (en) * 1988-02-18 1990-07-03 Siemens Aktiengesellschaft Nuclear reactor fuel assembly
US5084234A (en) * 1988-12-31 1992-01-28 Hoesgen Karlheinz Absorption casing for a source of radioactive radiation, particularly for a nuclear reactor
US4986957A (en) * 1989-05-25 1991-01-22 General Electric Company Corrosion resistant zirconium alloys containing copper, nickel and iron
US5024809A (en) * 1989-05-25 1991-06-18 General Electric Company Corrosion resistant composite claddings for nuclear fuel rods
US5026516A (en) * 1989-05-25 1991-06-25 General Electric Company Corrosion resistant cladding for nuclear fuel rods
US5073336A (en) * 1989-05-25 1991-12-17 General Electric Company Corrosion resistant zirconium alloys containing copper, nickel and iron
US5373541A (en) * 1992-01-17 1994-12-13 Framatome Nuclear fuel rod and method of manufacturing the cladding of such a rod
US5493592A (en) * 1992-03-13 1996-02-20 Siemens Aktiengesellschaft Nuclear-reactor fuel rod with double-layer cladding tube and fuel assembly containing such a fuel rod
WO1993018520A1 (en) * 1992-03-13 1993-09-16 Siemens Aktiengesellschaft Nuclear reactor fuel rod with double layer cladding tube
US5247550A (en) * 1992-03-27 1993-09-21 Siemens Power Corporation Corrosion resistant zirconium liner for nuclear fuel rod cladding
US5887045A (en) * 1995-01-30 1999-03-23 Framatome Zirconium alloy tube for a nuclear reactor fuel assembly, and method for making same
US5711826A (en) * 1996-04-12 1998-01-27 Crs Holdings, Inc. Functionally gradient cladding for nuclear fuel rods
US6319339B1 (en) 1997-03-25 2001-11-20 Framatome Anp Inc. High strength zirconium alloys containing bismuth
US5790623A (en) * 1997-03-25 1998-08-04 Siemens Power Corporation Composite cladding for nuclear fuel rods
US5772798A (en) * 1997-03-25 1998-06-30 Siemens Power Corporation High strength zirconium alloys containing bismuth
US5768332A (en) * 1997-03-27 1998-06-16 Siemens Power Corporation Nuclear fuel rod for pressurized water reactor
US5787142A (en) * 1997-04-29 1998-07-28 Siemens Power Corporation Pressurized water reactor nuclear fuel assembly
US6511556B1 (en) 1998-06-12 2003-01-28 Siemens Power Corporation High strength zirconium alloys containing bismuth and niobium
US20050005872A1 (en) * 2003-07-09 2005-01-13 Greeson John Stuart Automated carrier-based pest control system
US20060048869A1 (en) * 2004-09-08 2006-03-09 David White Non-heat treated zirconium alloy fuel cladding and a method of manufacturing the same
US20060048870A1 (en) * 2004-09-08 2006-03-09 David White Zirconium alloy fuel cladding for operation in aggressive water chemistry
US8043448B2 (en) 2004-09-08 2011-10-25 Global Nuclear Fuel-Americas, Llc Non-heat treated zirconium alloy fuel cladding and a method of manufacturing the same
US9139895B2 (en) 2004-09-08 2015-09-22 Global Nuclear Fuel—Americas, LLC Zirconium alloy fuel cladding for operation in aggressive water chemistry
US20110002433A1 (en) * 2006-08-24 2011-01-06 Lars Hallstadius Water Reactor Fuel Cladding Tube
US8320515B2 (en) 2006-08-24 2012-11-27 Westinghouse Electric Sweden Ab Water reactor fuel cladding tube

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DE3668251D1 (en) 1990-02-15
EP0212351B1 (en) 1990-01-10
JPH065311B2 (en) 1994-01-19
EP0212351A1 (en) 1987-03-04
JPS6235287A (en) 1987-02-16
DE3528545A1 (en) 1987-02-19

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